ML15239A023

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Forwards Summary of Presentation at 890421 Meeting Re SALP Repts 50-269/89-01,50-270/89-01 & 50-287/89-01 for Aug 1987 to Jan 1989.Decline Apparent in Effectiveness of Security & Safeguards Programs.No Change Made to SALP Rating
ML15239A023
Person / Time
Site: Oconee  
Issue date: 06/29/1989
From: Ebneter S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Tucker H
DUKE POWER CO.
Shared Package
ML15239A024 List:
References
NUDOCS 8907120089
Download: ML15239A023 (38)


See also: IR 05000269/1989001

Text

ACCELERATED

DISTRIBUTION

DEMONSTRATION

SYSTEM

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8907120089

DOC.DATE: 89/06/29 NOTARIZED: NO

DOCKET #

FACIL:50-269 Oconee Nuclear Station, Unit 1, Duke Power Co.

05000269

50-270 Oconee Nuclear Station, Unit 2, Duke Power Co.

05000270

50-287 Oconee Nuclear Station, Unit 3, Duke Power Co.

05000287

AUTH.NAME

AUTHOR AFFILIATION

EBNETER,S.D.

Region 2, Ofc of the Director

IR

RECIP.NAME

RECIPIENT AFFILIATION

TUCKER,H.B.

Duke Power Co.

SUBJECT: Forwards summary of presentation at 890421 meeting re SALP

D

Repts 50-269,270 & 287/89-01 for Aug 1987 -

Jan 1989.

DISTRIBUTION CODE: IE40D COPIES RECEIVED:LTR 4 ENCL _

SIZE:

2

S

TITLE: Systematic Assessment of Licensee Performance ,(.SALP) Report

NOTES:

RECIPIENT

COPIES

RECIPIENT

COPIES

ID CODE/NAME

LTTR ENCL

ID CODE/NAME

LTTR ENCL

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PD2-3 LA

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TOTAL NUMBER OF COPIES REQUIRED: LTTR

33

ENCL

.32

Docket Nos. 50-269, 50-270, 50-287

License Nos. DPR-38, DPR-47, DPR-55

Duke Power Company

ATTN:

Mr. H. B. Tucker, Vice President

Nuclear Production Department

422 South Church Street

Charlotte, NC 28242

Gentlemen:

SUBJECT: SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE (NRC INSPECTION REPORT

NOS. 50-269/89-01, 50-270/89-01 AND 50-287/89-01)

This refers to the NRC's Systematic Assessment of Licensee Performance (SALP)

report for your Oconee facility which was sent to you on April 11,

1989; our

meeting of April 21, 1989, at which we discussed the report; and your written

comments dated May 19, 1989.

I have enclosed a summary of our presentation at

the meeting, a copy of your written comments,

a copy of-the slides which were

used at the presentation, and the Final SALP report for the period August 1,

1987 -

January 31, 1989.

We appreciate your efforts in evaluating the interim SALP report and providing

corrections and clarification.

The following is our evaluation of your

comments:

Maintenance Surveillance

In your response, you expressed disappointment in the decline of the SALP

rating in this area.

You stated that your performance, although not

perfect, improved during the last SALP period and that this improvement

has continued through the current period.

We agree that the maintenance and surveillance programs are strong at

Oconee and over the SALP period Oconee had good availability and few

operational problems directly attributable to maintenance.

We also

acknowledge that your maintenance performance may not have declined since

the last SALP period.

As reflected in the SALP report, our perception of your performance~may

have changed because of the unusually intensive inspections which- fvealed

previously unrecognized problems.

Therefore, we continue to believe that

a Category 2 rating is appropriate.

FIA

AFDC

Duke Power Company

2

JUN 2 9 189

Security and Safeguards

In your response to the security area,

you again expressed your

disappointment in the SALP rating given.

You stated that you do not

believe your lack of resolution of the long-standing issue relating to the

assessment capability of the closed circuit television (CCTV)

and the

increase in the number of violations attributable to personnel error are

significant enough to result in the need to reduce the SALP rating from

the previous review period.

Although no single problem identified during the SALP period was overly

significant, the number of problems identified showed a distinct decrease

in the effectiveness of the security effort. Regarding the CCTV assess

ment, we do not agree that a lack of adequate CCTV assessment is a minimal

security system vulnerability.

A CCTV system is called for in the

regulations to facilitate initial response to an alarm and assessment of

threat, "to limit exposure of responding personnel to possible attack."

You have relied on compensatory measures, the use of responding guards, to

provide alarm assessment since identification of the problem almost two

years ago.

A compensatory measure is meant to be a short-term measure

providing the same or greater level of security prior to the degradation.

The use of responding guards does not provide immediate assessment as

CCTVs

could.

Although this finding resulted from the Regulatory

Effectiveness Review conducted in September 1985, the lack of

aggressiveness in pursuing long-term resolution of this issue continued

during this SALP period.

In your discussion of the violations issued during the SALP period, you

state that six of the violations were licensee-identified and should not

have been cited. Although they were identified by you, this is only one

criteria evaluated when deciding whether or not to issue a violation.

Additionally, you state that the violations do not reflect exploitable

weaknesses.

The issue of exploitability is considered when assigning a

severity level, not in whether to issue the violation.

Based on our evaluation in the SALP report and the discussion above, we

feel there has been a decline in the overall effectiveness in the Security

and Safeguards programs at Oconee and there should be no change in the

SALP rating.

In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2,

Title 10,

Code of Federal Regulations,

a copy of this letter with the

enclosures will be placed in the NRC's Public Document Room.

Duke Power Company

3

No reply to this letter is required; however, should you have any questions

concerning these matters, I will be pleased to discuss them with you.

Sincerely,

Stewart D. Ebneter

Regional Administrator

Enclosures:

1. SALP Presentation Meeting Summary

2. Written Comments Received

from Licensee

3. Copy of SALP Presentation

Slides

4.

Errata Sheet

5.

Final SALP Report as Revised

from Interim Report

cc w/encls:

M. S. Tuckman, Station Manager

State of South Carolina

bcc w/encl:

NRC Resident Inspector

L. Wiens, NRR

Document Control Desk

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ENCLOSURE 1

A. A meeting was held on April 21,

1989 at the Oconee site to discuss the

SALP Report for the period August 1, 1987 - January 21, 1989.

B. Licensee Attendees

W. H. Owen, Executive Vice President, Engineering and Construction

H. B. Tucker, Vice President, Nuclear Production

T. C. McMeekin, Vice President, Engineering

G. W. Grier, Manager, Quality Assurance

M. S. Tuckman, Station Manager, Oconee

C. NRC Attendees

S. D. Ebneter, Regional Administrator, Region II (RH)

C. W. Hehl, Deputy Director, Division of Reactor Projects (DRP), RII

A. R. Herdt, Chief, Reactor Projects Branch 3, DRP, RH

D. B. Matthews, Director, Project Directorate 11-3,

Office of Nuclear Reactor Regulation (NRR)

L. Wiens, Oconee Project Manager, Project Directorate 11-3, NRR

P. A. Skinner, Senior Resident Inspector, Oconee,

DRP, RII

L. D. Wert, Resident Inspector, Oconee, DRP, RH

ENCLOSURE 3

UNITED STATES

NUCLEAR REGULATORY

COMMISSION

SYSTEMATIC ASSESSMENT

OF

LICENSEE PERFORMANCE

(SALP)

DUKE POWER

COMPANY

AUGUST 1, 1987 through JANUARY 31, 1989

OCONEE UNITS 1, 2, AND 3

APRIL 21, 1989

SENECA , SOUTH CAROLINA

SALP PROGRAJI OBJECTIVES

1. IDENTIFY TRENDS IN LICENSEE PERFORMANCE

2. PROVIDE A BASIS FOR ALLOCATION

OF NRC RESOURCES

3. IMPROVE NRC REGULATORY. PROGRAM

asA

11

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BRANCH NO. 3

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ASSOC. DIRECTOR

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NRC

SALP PROGRAM

REVISIONS

MAJOR CHANGES TO THE

SALP PROGRAM CONSIST OF...

  • Redefinion of Functional Areas
  • Reduction in Number of Separate

Functional Areas

  • Two New Functional Areas
Engineering/Technical Ssupport
Safety Assessment/Quality Verification
  • Attributes Addressing Human Performance

and Self- Assessment

  • Emphasis on Analysis

PERFORMANCE ANALYSIS AREAS

FOR OPERATING REACTORS

1. PLANT OPERATIONS

2. RADIOLOGICAL CONTROLS

3. MAINTENANCE / SURVEILLANCE

4. EMERGENCY PREPAREDNESS

5. SECURITY

6. ENGINEERING / TECHNICAL SUPPORT

7. SAFETY ASSESSMENT / QUALITY. VERIFICATION

ENGINEERING/TECHNICAL SUPPORT

The purpose of this functional area

is to address the adequacy of technical

and engineering support for all plant

activities. It includes all Licensee

Activities associated with the design

of plant modifications; engineering and

technical support for operations, outages,

maintenance, testing, surveillance; and

procurement activities; training; and

configuration management (including

maintaining design bases and safety margins).

SAFETY ASSESSMENT/QUALITY VERIFICATION

The purpose of this functional area is to address the

technical adequacy and completeness of the licensee's

approach toward a va'iety of activities associated with

the implementation of licensee safety policies and

licensee activities related to amendment requests, exemption

requests, relief requests, response to generic letters,

bulletins, and information notices, and resolution of TMI

items and other regulatory initiatives. It also includes

licensee activities related to the resolution of safety

issues, 10 CFR 50.59 reviews, 10 CFR 21 assessments, safety

committee and self-assessment activities, analysis of

industry's operational experience, root cause analyses of

plant events, use of feedback from plant quality assurance

quality control(QA/QC) reviews, and participation in self

improvement programs. It includes the effectiveness of the

licensee's quality verification function in identifying

substandard or anomalous performance in monitoring the

overall performance of the plant.

PERFORMANCE RATING CATEGORIES

  • Expanded discussion intent
  • Redefinition of the categories to clarify

their meaning

AREA PERFORMANCE

CATEGORY I

UCENSEE MANAGEMENT ATTENTION AND INVOLVEMENT

ARE READILY EVIDENT AND PLACE EMPHASIS ON SUPERIOR

PERFORMANCE OF NUCLEAR SAFETY OR SAFEGUARDS

ACTMTIES WITH THE RESULTING PERFORMANCE SUB

STANTIALLY EXCEEDING REGULATORY REQUIREMENTS.

LICENSEE RESOURCES ARE AMPLE AND EFFECTIVELY USED

SO THAT A HIGH LEVEL OF PLANT AND PERSONNEL

PERFORMANCE IS BEING ACHIEVED. REDUCED NRC ATTENTION

MAY BE APPROPRIATE.

AREA PERFORMANCE

CA TECORY 2

LICENSEE MANAGEMENT ATTENTION TO AND INVOLVEMENT

IN THE PERFORMANCE OF NUCLEAR SAFETY OR SAFEGUARDS

ACTIVITIES ARE GOOD. THE UCENSEE HAS ATTAINED A

LEVEL OF PERFORMANCE ABOVE THAT NEEDED TO MEET

REGULATORY REQUIREMENTS. UCENSEE RESOURCES ARE

ADEQUATE AND REASONABLY ALLOCATED SO THAT GOOD PLANT

AND PERSONNEL PERFORMANCE IS BEING ACHIEVED. NRC

ATTENTION MAY BE MAINTAINED AT NORMAL LEVELS.

AREA PERFORMANCE

CA TECOR Y J

UCENSEE MANAGEMENT ATTENTION TO AND INVOLVEMENT

IN THE PERFORMANCE OF NUCLEAR SAFElY OR SAFEGUARDS

ACTMTIES ARE NOT SUFFICIENT. THE UCENSEE'S

PERFORMANCE DOES NOT SIGNIFICANTLY EXCEED THAT NEEDED

TO MEET MINIMAL REGULATORY REQUIREMENTS. UCENSEE

RESOURCES APPEAR TO BE STRAINED OR NOT EFFECTIVELY

USED. NRC ATTENTION SHOULD BE INCREASED ABOVE NORMAL

LEVELS.

OPERATIONS PHASE, VIOIATIONS/OPERATING REACTOR

AUGUST 1, 1987 through JANUARY 31, 1989

40

LEGEND

35

R II AVE

N

OCONEE

30.-UT1ITIES

OU

b.

0

GPC

FPL

R1l AV

SCE

APC

FPC

VEP

OCONEE

CPL

SERI

ULIUTY

ALLEGATIONS PER UTILITY/SITE

AUGUST 1, 1987 through JANUARY 313 1989

2

LEGEND

RII AVE.

Is.

OCONEE

UTIUTIES

O 14

z

0

< 12'

LTII

0

I

w

4

GPC

SERI

VEP

APC

OCONEE

FPL

RII AVE.

CPL

FPC

SCE

UTILITY

EVALUATION CRITERIA

1. MANAGEMENT INVOLVEMENT IN ASSURING QUAITY

2. APPROACH TO RESOLUTION OF TECHNICAL ISSUES

FROM A SAFETY STANDPOINT

3. RESPONSENESS TO NRC INITIATIVES

4. ENFORCEMENT HISTORY

5. REPORTING AND ANALYSIS OF REPORTABLE EVENTS

6. STAFFING (INCLUDING MANAGEMENT)

7. TRAINING EFFECTIVENESS AND QUALIFICATION

VIOLATION SUMMARY

AUGUST 1, 1987 through JANUARY 31, 1989

1i

111V

v

OCONEE UNIT 1

0

0

1

16

5

OCONEE UNIT 2

0

0

1

16

5

OCONEE UNIT 3

0

0

1

19

7

REGION11 AVE.

0

0

2

20

5

PER UNIT

LERs PER UNIT

AUGUST 1, 1987 through JANUARY 31,1989

40

38

LEGEND

a

NATL AVE.

34

33

OCONEE

PLANT TYPE

25

21

0

w

hJ

0

z Z 15

10

10

GE

WE NATL AVE.

CE

BW

OCONEE

PLANT TYPE

OCONEE LERs

AUGUST 1,

1987 through JANUARY 31, 1989

a

29

LEGEND

PERSONNEL (other) = 4

PERSONNEL (test/cal)

6

PERSONNEL (maintenance)

2

O7 PERSONNEL (operating)

3

OTHER = 3

S15

COMPONENT FAILURE = 4

DESIGN / CONST. = 7

z

U

PERSONNEL (total) x 15

PLANT

PERSONNEL

OCONEE LERs

(PLANT)

AUGUST 1, 1987 through JANUARY 31, 1989

DG/NPERSONNEL

5C1A.7%

OTHER

1 0.3%

24.1%

1 3.8%

DESIGN/CONST.

COMP. FAILURE

OCONEE LERS

(PERSONNEL)

AUGUST 1, 1987 through JANUARY 31, 1989

TEST/CALIB.

40%

MAINTENANCE

13.3%

OPERATIONS

OTHER

20%

28.7%

FUNCTIONAL AREA COMPARISON

FOR REGION 11 FACILITIES

CYCLE VI

14

LEGEND

121

ECATEGORY 1

CATEGORY 2

to

.

CATEGORY 3

O

Z

.

W",

WO

z

4

2

9--

-1

00

00

0

OPS

MAINT

EM PREP

RAD CON

SURV

FIRE PROT

FUNCTIONAL AREA

FUNCTIONAL AREA COMPARISON

FOR REGION 11 FACILITIES

CYCLE VI

14

LEGEND

12

E CATEGORY 1

CATEGORY 2

to

CATEGORY 3

0O

to

z

2

00

0

00

SEC

OUTAGES

QP

UC

TRNG ENGR SUP

FUNCTIONAL AREA

PLANT OPERATIONS - CATEGORY 1

o

OVERALL PLANT OPERATIONS WAS A STRENGTH

o

MANAGEMENT

SUPPORT AND

INVOLVEMENT

IN ALL ASPECTS OF

PLANT OPERATIONS WERE EVIDENT

o

CONTROL ROOM DEMEANOR AND ATTENTIVENESS WERE GOOD

o

CONTINUED REDUCTION IN AUTOMATIC REACTOR TRIPS

o

EMERGENCY PROCEDURES AND ABNORMAL PROCEDURES ADEQUATE

o

WEAKNESSES IDENTIFIED IN COMMUNICATIONS, AND TRAINING OF

OPERATORS AND SUPERVISORS

o

IMPLEMENTATION OF FIRE PROTECTION PROGRAM MET NRC

COMMITMENTS

o

PLANT HOUSEKEEPING CONTINUED TO IMPROVE

RADIOLOGICAL CONTROLS - CATEGORY 1

o

STRONG MANAGEMENT SUPPORT AND INVOLVEMENT

o

AGGRESSIVE CONTAMINATION CONTROL PROGRAM

o

COLLECTIVE DOSE LOWEST SINCE 1975

o

RADIOACTIVE EFFLUENTS WERE WITHIN REGULATORY LIMITS

o

WEAKNESSES INDENTIFIED IN CONTROL OF ACCESS TO RADIATION

AREAS

o

ATTENTION

TO OPERATION AND MAINTENANCE

OF PROCESS AND

EFFLUENT MONITORS NOT SUFFICIENT

MAINTENANCE/SURVEILLANCE -

CATEGORY 2

o

OVERALL MAINTENANCE/SURVEILLANCE PROGRAMS WERE EFFECTIVE

o

MANAGEMENT SUPPORT AND INVOLVEMENT IN MAINTENANCE

PROGRAM WAS APPARENT

o

QUALITY OF MAINTENANCE

AND SURVEILLANCE

PLANNING WAS

GOOD

o

WEAKNESSES

IDENTIFIED

IN 50.59

REVIEWS

AND

COMMUNICATION/COORDINATION

o

NUMEROUS

MAINTENANCE

PERFORMANCE

PROBLEMS

WERE

IDENTIFIED

o

PERFORMANCE IN THE SURVEILLANCE AREA MIXED

EMERGENCY PREPAREDNESS -

CATEGORY 1

o

DEMONSTRATED

OVERALL ABILITY TO IMPLEMENT

THE CRITICAL

ASPECTS

OF

EMERGENCY

PREPAREDNESS

DURING

SIMULATED

ACTUAL EMERGENCY EVENTS

o

SATISFACTORY

PERFORMANCE

DURING APRIL 1988 FULL SCALE

EXERCISE

o

WEAKNESS NOTED FOR INCORRECT EMERGENCY CLASSIFICATION

o

SATISFACTORY

CAPABILITY

FOR

PROMPT

NOTIFICATION

AND

EFFECTIVE COMMUNICATIONS

o

A STRONG COMMITMENT TO EP TRAINING NOTED

SECURITY AND SAFEGUARDS -

CATEGORY 2

o

AUTHORITIES

AND RESPONSIBILITIES

WERE CLEARLY DEFINED

AND EFFECTIVE

o

CONTRACT FORCE ADEQUATELY STAFFED AND APPROPRIATELY

TRAINED AND EQUIPPED

o

INDEPENDENT AUDITS THOROUGH

o

CONCERN REGARDING CCTV ASSESSMENT CAPABILITY

o

RELIANCE ON LONG TERM COMPENSATORY MEASURES NOTED

o

ADHERENCE TO PROCEDURES AND DOCUMENTATION PROBLEMS

o

ADEQUATE SAFEGUARDS PROGRAM FOR THE CONTROL OF BOTH FUEL

AND NON-FUEL SNM

ENGINEERING AND TECHNICAL SUPPORT -

CATEGORY 2

o

ENGINEERING AND TECHNICAL SUPPORT WAS GENERALLY GOOD

o

DESIGN

ENGINEERING

ACTIVITY

RESULTED

IN A NUMBER OF

SELF-IDENTIFIED PROBLEMS AND IMPROVEMENT INITIATIVES

o

MAINTENANCE ENGINEERING SUPPORT EFFECTIVE

o

OVERALL QUALITY OF ENGINEERING

AND TECHNICAL

SUPPORT

COMPROMISED BY WEAKNESSES IN COMMUNICATION

o

OPERATOR TRAINING AND REQUALIFICATION TRAINING PROGRAMS

GENERALLY GOOD

o

SIMULATOR TRAINING STAFF SUPPLEMENTED

WITH EXPERIENCED

OPERATORS

o

SIMULATOR GENERALLY UPDATED HOWEVER MINOR HARDWARE AND

SOFTWARE NON-CONFORMANCES IDENTIFIED

SAFETY ASSESSMENT/QUALITY VERIFICATION -

CATEGORY 2

o

MANAGEMENT INVOLVEMENT IN LICENSING ACTIVITIES EVIDENT

o

ACTIVE PARTICIPANT AND LEADER

FOR INDUSTRY

INVOLVEMENT

IN GENERIC ISSUES

o

CONCERN REGARDING TIMELY RESOLUTION OF ISSUES FOR OCONEE

o

LERS

SUBMITTED

WERE

GENERALLY

WELL WRITTEN

AND

HAD

SUFFICIENT DEPTH

o

TIMELY, SOUND RESPONSES TO GENERIC LETTERS AND BULLETINS

o

DEMONSTRATED

CAPABILITY

TO IDENTIFY AND RESOLVE PLANT

PROBLEMS

o

10 CFR 50.59 EVALUATION PERFORMANCE MIXED

o

COMMUNICATIONS

HAVE

HINDERED

RESOLUTION

OF PROBLEMS;

IMPROVEMENT NOTED DURING LATTER PORTION OF PERIOD

SUMMARY OF RESULTS

o

OVERALL, PLANT WAS OPERATED IN A SAFE MANNER

o

STRENGTHS IN THE AREAS OF PLANT OPERATIONS, RADIOLOGICAL

CONTROLS AND EMERGENCY PREPAREDNESS

o

IMPROVEMENTS

IN THE AREA OF SAFETY ASSESSMENT/QUALITY

VERIFICATION

o

PROGRESS IN THE AREA OF ENGINEERING TECHNICAL SUPPORT,

HOWEVER WEAKNESSES STILL EXIST SUCH AS THOSE ASSOCIATED

WITH COMMUNICATIONS

o

MAINTENANCE/SURVEILLANCE AND SECURITY PROGRAMS VIEWED AS

STRONG,

HOWEVER A DECLINE IN PERFORMANCE

WAS NOTED IN

THESE AREAS